Status of design and strategy for CFETR

Minyou Ye and

CFETR Design Group

School of Nuclear Science and Technology, USTC P. R. China

Email: yemy@ustc.edu.cn, myye@ipp.ac.cn

26 -28 March 2013 Kyoto Japan

SNST-USTC

Content

Introduction

background

opinion and consideration

Progress on the concept design of CFETR

Summary

SNST-USTC

What should be the next step for MFR in China ?

SNST-USTC Background

• Significant progress of fusion research has been achieved within last 50 years; • International Thermonuclear Experimental Reactor (ITER) has been approved for construction by 7 partners. • In China many important progresses on tokamaks (e.g. EAST, HL-2A) have been achieved during last 20 years;

• China is facing serious energy problem (energy shortage and

environment pollution). Which will be even more serious in the near future;

• Chinese government made the decision to join in ITER. The purpose is

to promote the development of the fusion energy for ultimate use as early

as possible;

• Therefore the National Integration Design group for Magnetic

Confinement Fusion Reactor has been founded in 2011

• The design activities of the Chinese Fusion Engineering Test Reactor

(CFETR) as the next step are under way by the group.

SNST-USTC Background

Head: Wan Yuanxi Li,Jiangang Liu Yong, Wang, Xiaolin

National design group

Vice heads

Wan,Yuanxi USTC, ASIPP

Li, Jiangang ASIPP, USTC

Liu, Yong SWIP

Wang, Xiaolin CAEP

Ye, Minyou USTC

Wan, Baonan ASIPP

Duan, Xuerun SWIP

Yu, Qin quang Germany

Zhuang, Ge HUST

Yang, Qinwei SWIP

Wu, Songtao ITER

Li, Qiang SWIP

Weng, Pede ASIPP

Guo, Huoyang USA

Feng, Kaiming SWIP

Wan, Farong BUST

Fu, Pen ASIPP

Wu,Yican USTC

Gong, Jun INS

SNST-USTC

Headquarter ： SNST-USTC

2011- 2014: provide two options of engineering concept design of CFETR which should include in:

• Missions • Type • Main physics basis • Main techniques basis to be taken • The concept engineering design for all sub-systems • Budget & Schedule • Location • Management system • List of the key R&D items • The plan for 200 PhD students / year

2015: will make the proposal to government to try to get permission for CFETR construction;

Working task and schedule SNST-USTC

Support system for fusion research in China

Content

Introduction

background

opinion and consideration

Progress on the concept design of CFETR

Summary

SNST-USTC

Final goal is to obtain realistic FE (FPP)

The steps for going to fusion energy ( FPP)

If the fusion energy is goal the necessary steps should be :

1.achieve the burning plasma :

high density n ; high temperature T i ; high energy and particle confinement τ E ;

2. sustain the burning plasma to be SSO or long pulse with high duty cycle :

CW heating : α particles or external heating such as NBI, RF? CW CD: bootstrap CD ? or external inductive or no-inductive ? “continual” fueling CW exhausting the ash of burning by divertor CW extracting the particle’s energy by divertor CW extracting the fusion neutron energy by blanket via first wall

3.Tritium must be self–sustainable by blanket ;

4. The materials of first wall and blanket have suitable live time ;

Before ITER The most important issue for fusion research is

to improve the confinement

τE , p

---------------------------------------------------------------------------------------

The most important issue for fusion energy is to sustain the burning time

tburning

Practical energy resources should be SSO !!

The long burning time for FE is a basic requirement

tburning ---------------------------------------------------------------------------------------------------------------

Are there good physic and technology basis for SS burning plasma operation ? Answer is no !!

And how to achieve ? ----------------------------------------------------------------------------------------------

How to achieve the T- self-sustain by Blanket ?

What will be happened for key in-vessel components and related materials under high flux irradiation by 14 MeV neutrons ?

ITER is the burning plasma device and its scientific goals are: • to produce a plasma dominated by α-particle heating • produce a significant fusion power amplification factor (Q ≥10) in long-pulse operation (300 - 500s) • aim to achieve steady-state operation of a tokamak (Q=5) • retain the possibility of exploring controlled ignition (Q≥30) • demonstrate integrated operation of technologies for a fusion power plant • test components required for a fusion power plant • test concepts for a tritium breeding module

The scientific goals of ITER

Even if ITER can make great contribution to long pulse or SSO burning plasma but it is mainly on physics and not on real fusion energy because of the real burning time during 14 year D-T operation is only about 4 %, which results in :

1. There is no enough fusion energy produced for utilization. 2. As the consequent the total neutron flux is not enough to

demonstrate the real tritium breeding for tritium self sustainable by blanket.

3. No enough neutrons to do the material tests in high flux fusion neutron radioactive environments.

4. Therefore there only are shielding blankets for ITER. 5. Even if adding the TBM with addition budget but it is

only concept testing for tritium breeding and not real self sustainable blanket and related material tests

Gaps between ITER and FPP

Conclusion: the engineering test reactor is necessary to be

constructed parallel with or after ITER and before the

fusion power plant (FPP).

For this purpose the China Fusion Engineering Test

Reactor (CFETR) is under discussion seriously for design

and construction.

The CFETR must be built before the FPP in China

ITER can be a good basis for CFETR both on SSO burning

plasma physics and some technologies;

The goals of CFETR should be different with ITER and aim to

the problems related with fusion energy

Both physic and technical basis of the CFETR should be more

realistic when it is designed.

CFETR should not make over-promise, it just is a important

engineering test reactor for future DEMO or FPP for FE

Common understanding (1)

So mission must be realistic and sequence must be right !!

The cost for fusion energy , the multi application of blanket

could be lower priority in compare with T selves- sustainable

and heat conversion and extracted;

The divertor will be another key component for the success of

future FPP- it will be the most important components related

with the basic requirements for SSO both on physics and

technologies.

Common understanding (1)

Content

Introduction

some background information

opinion and consideration

Progress on the concept design of CFETR

Summary

1. A good complement to ITER； 2. Relay on the existing ITER physical and technical bases ; 3. Fusion power Pf = 50～200MW； 4. Steady-state or long pulse operation (duty cycle ≥ 0.3- 0.5)； 5. Demonstration of full cycle of T self-sustained with TBR ≥ 1.2; 6. Exploring options for DEMO blanket & divertor with an easily changeable capability by RH. CFETR will be the important facility to bridge from ITER to DEMO in China, which is necessary step to go to DEMO and then the fusion power plant.

The mission and design goal of CFETR

Preliminary design consideration

1. Physics consideration

2. Integrated design consideration

of the device with RH

3. Blanket considerations

4. Divertor considerations

5. Tritium consideration

• CFETR as a test reactor to achieve the fusion energy at reasonable fusion power level should have high reliability and availability. So the core plasma designs are based on relatively conservative physics and technology assumptions, such as operation far away from the stability limits and readily achievable performance；

• A device of R=5.7m, a=1.65m in size with Bt=5T and total H&CD source power of 80MW (assumed efficiency 0.8) with SN configuration could be projected based on a zero-dimensional system study using extrapolations of current physics, which are from the multi-iteration and optimization among plasma performance, blanket module and superconducting magnet requirements, etc.

• Analysis of vertical stability control indicates that the basis configuration with an elongation kx=2.0 can be reliably controlled using in-vessel coil similar to that used in EAST.

Physics consideration

key parameters and several design versions of CFETR are under comparison

CFETR

Major radius (m) 5.7 Minor radius (m) 1.65 Elongation 1.8 – 2.0 Plasma current (MA) 8-10 Toroidal field (T) 5.0/4.5 Elonation 1.8-2.0 Triangularity 0.4 Heating Power (MW) 80/100 Fusion power (MW) 50~200 Plasma volume (m3) 612 Flux(Vs) 160

R(m)=5.7, a(m)=1.65, B(T)=5； κ=2.0, δ=0.4； αn=1, αT=1；Vp(m3)=612； Ip=10MA，q95=4.17, Zeff~1.76，Power deposition 80%， gCD = 0.16~0.26 (ITER target 0.4)

Simple scaling for Parameter investigation

B.N. Wan et al.,

Ip~8MA, Bt=5T, q95=5.2, Zeff~1.76， P~80*0.8MW， γCD = 0.15~0.22 (ITER target 0.4)

Conclusion·：

• Scenario analysis based on “ITER physics design guidelines” show that CFETR can achieve 200MW fusion power at Ip~10MA in H-mode for over 1000s；

• 8.5MA in “improved H-mode" (H98~1.2) for several hours or at Ip~7.5MA for steady-state in advanced regime with a moderate factor of H98~1.3 and beta_N <2.8.

key parameters and several design versions of CFETR are under comparison

CFETR

Major radius (m) 5.7 Minor radius (m) 1.65 Elongation 1.8 – 2.0 Plasma current (MA) 8-10 Toroidal field (T) 5.0/4.5 Elonation 1.8-2.0 Triangularity 0.4 Heating Power (MW) 80/100 Fusion power (MW) 50~200 Plasma volume (m3) 612 Flux(Vs) 160

Range of key parameters and several design versions of CFETR are under comparison

Preliminary design consideration

1. Physics consideration

2. Integration consideration of the tokamak device with RH

3. Blanket considerations

4. Divertor considerations

5. Tritium consideration

The duty cycle of CFTER will be

impacted

by the principle of RH significantly

The structure of Case 1 for CFETR The structure of Case 2 for CFETR The structure of Case 3 for CFETR

RH conceptual design for big window style strategy

RH conceptual design for big window style strategy

RH conceptual design for medium window style strategy

RH conceptual design for Upper port strategy

RH conceptual design for Upper port strategy

Preliminary design consideration

1. Physics consideration

2. Integration consideration of the tokamak device with RH

3. Blanket considerations

4. Divertor considerations

5. Tritium consideration

Group I:

1) HC (8MPa, 300/5000C), Li4SiO4 (Li2TiO3 ), Be , RAFM

Group II :

1) SLL ( ~150 0 C ) , CLAM

2) DLL( ~700 0C), CLAM

Group III :

1) HC, Li4SiO4 , Be , RAFM

2) WC, Li2TiO3, Be12Ti , RAFM

Three groups are working on the concept design of CFETR blanket

Group I: HC (8MPa, 300/5000C), Li4SiO4 (Li2TiO3 ), Be , RAFM

Group II: SLL ( ~150 0 C ) , CLAM DLL( ~700 0C), CLAM

phase II and III

Group III: 1) HC, Li4SiO4 , Be , RAFM 2) WC, Li2TiO3, Be12Ti , RAFM

NWL （average）: 0.33 MW/m2

Inboard shielding thickness : ～ 46 cm

Outboard shielding thickness: ～40cm Inboard breeder thickness: ～ 37cm outboard breeder thickness: ～ 67cm TBR can ≧ 1.2 but very sensitive by outboard windows TBR is impacted by first wall material and thickness; Difference between 1 D and 3D calculations ～ 15-20%

Conclusions

Preliminary design consideration

1. Physics consideration

2. Integrated design consideration

of the device with RH

3. Blanket considerations

4. Divertor considerations

5. Tritium consideration

Main Functions of Divertor

Exhaust the major part of the plasma thermal power, reducing heat flux below limitation of target materials (10 MW/m2).

Remove fusion helium ash from core plasma while providing sufficient screening for impurities influxes.

Maintain acceptable erosion rate in terms of reactor lifetime.

Considerations of Divertor Design of CFETR

CFETR divertor

configurations:

bottom SN

Advantages of SN:

• more simple

• lager volume of pl.

• benefit on TBR

Key issues for divertor design

ITER-like divertor

Advanced divertor

The power exhaust (estimated for CFETR)

Power handling is the most important issue for the reactor design

Power handling [MW] Pfusion 200

Pa 40

Paux 100

Pradcore (brem+sync.) 40

Pout= Pa+Paux–Pradcore 100

Pout/Rp [MW/m]

17

Pdiv (= Pout–PradDiv&Edge )

for = Awet = 1 m2. <10

⇒ PradDiv&Edge >90

Pfus= 200 MW Pheat=100+40 MW

Prad= 40 MW

100MW

Divertor plates

Injected power (auxiliary heating: 100 MW)

Advanced Divertor Configurations

New options: Super-X, Snowflake

Advantages: •Increase wetted area to reduce peak heat flux •Increase L// to facilitate radiative divertor.

Issues to be addressed: •Minimum number of PF coils •PF current and size •Restrictions of poloidal coil location

Ip [MA] 10 R[m] 5.7 a[m] 1.6 βp 1.01 ιi 1.09 k 2.0 δ 0.4/0.62 Rxpt [m] 4.692 Zxpt[m] -3.134

Single null

Ip [MA] 10 R[m] 5.7 a[m] 1.59 βp 0.80 ιi 1.09 k 2.01 δ 0.45/0.67 Rxpt [m] 4.637 Zxpt[m] -3.129

Snowflake (LSN)

Preliminary design consideration

1. Physics consideration

2. Integrated design consideration

of the device with RH

3. Blanket considerations

4. Divertor considerations

5. Tritium consideration

Summary of tritium inventories (maximum instantaneous values for each system; not all simultaneous)

• Type of inventory Maximum values (g T) • In-vessel 450 • Fuelling system 55 • Mechanical vacuum pumps (VPS) 20 • Torus exhaust processing (TEP) 30 • Isotope separation system (ISS) 220 • Storage and delivery system (SDS) 480 • Other systems (<15 g each) 28 • Estimated subtotal for FC systems 833 • Long term storage 2×450 • Hot cell and waste treatment 250 -------------------------------------------------------------- ---------------- • Total 2433

Assume : fraction of burn up 5% ; Reserve time : one day

First inventory of T: ~ 2000 g

Summary of tritium inventories (maximum instantaneous values for each system; not all simultaneous)

Type of inventory [g-T] ----------------------------------------------------------------------------------- • Mobilizable in-vessel (in PFC’s, • dust, co-deposited etc.) 330 • Cryopumps open to VV 120 Subtotal in-vessel 450 • Fuel cycle • Pellet fuelling (PIS) 45 • Gas fuelling (GIS) 10 • Mechanical vacuum pumps (VPS) 20 • Torus exhaust processing (TEP) 30 • Isotope separation system (ISS) 220 • Test blanket module tritium recovery (TBM-TRS) ~15 • Water detritiation (WDS) ~10 • Atmosphere detritiation (ADS) ~1 • Gas analysis (ANS) ~2 • Estimated subtotal for FC systems ~ 353 Subtotal of fuel cycle (project guideline) 450 Long term storage 2* 450 • Hot cell and waste treatment 200 • Tritium recovery and waste storage 50 Subtotal, hot cell and waste treatment 250

Content

Introduction

some background information

opinion and consideration

Progress on the concept design of CFETR

Summary

1. SSO or long operation with high duty cycle of the burning plasma is the most important issues both for the physics and related technologies for MFE development:

2. Missions required for CFETR should be more realistic and aim to the most important challenges for FE;

3. CFETR should be a good complement to ITER and it will demonstrate the fusion energy with a minim Pf = 50～200MW; long pulse or steady-state operation with duty cycle time ≥ 0.3～0.5; demonstrating the full cycle of T self-sufficiency with TBR ≥ 1.2; relay on the existing ITER physical and technical bases ; exploring options for DEMO blanket & divertor with an easy changeable core by RH.

Summary-1

4. The design choices of CFETR are still open;

5. The goal of CFETR design activities is to make a proposal

at the end of 2014 to government to try to get permission for

construction with the key R&D items for CFETR;

CFETR will be the important facility to bridge from

ITER to DEMO in China, which is necessary step to

go to DEMO and then the fusion power plant FPP.

Summary-2

Thanks for your

attention !